ML17277B477
| ML17277B477 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/13/1984 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17277B479 | List: |
| References | |
| NUDOCS 8408270501 | |
| Download: ML17277B477 (21) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM D CK N
0-397 WPPSS NUCLEAR PROJECT HO.
2 AMENDING HT T F CILI PER TING ICENSE License Ho. NPF-21 Amendment No.
4 E
1.
The NucIear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Washington Public Power Supply System (WPPSS, also the licensee) dated January 20, February 8 and Hay 4, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
Th'e facility will operate in conformity with the application as
- amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulation set forth in 10 CFR Chapter I; D.
The issuance, of this amendment will not be inimical to the common, defense and security or the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment, to this license amendment and paragraph 2.C.(2) of the Facility Operating License Ho.
NPF-21 is hereby amended as follows:
(2)
Technical S ecifications and Environmental Protection, Plan The TechnicaI Specifications contained in Appendix A, as revised through Amendment Ho. 4, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This amendment was effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
A. Schwencer, Chief Licensing Branch No.
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ATTACHMENT TO LICENSE AllENDMENT NO.
4 N..N -1 DOCKET NO. 50-397 Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3/4 3-93 3/4 3-94 3/4 3-95 3/4 6-22 3/4 6-31 3/4 8-3 3/4 8-18 3/4 9-3
'-7 3/4 3-93 3/4 3-94 3/4 3-95 3/4 6-22 3/4 6-31 3/4 8-3
'/4 8-18 3/4 9-3 6-7
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INSTRUMENT TABLE 4.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS CHANNEL MODES IN MHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE CHECK'HECK CALIBRATION TEST REIR E
Main a.
Condenser Offgas Post-Treatment Radiation Monitor Gross gamma detector alarm and D
automatic isolation of the offgas system outlet and drain valves R(2)
Q(1) 2.
Hain Condenser Offgas Pr e-Treatment. Radiation Honitor a.
Gamma sensitive ion chamber located D
M upstream of holdup line R(2)
Q(1) 3.
Hain a.
C.
d.
e.
Plant Release Monitor Noble Gas Activity Monitor 1)
Low Range 2)
Intermediate Range Iodine Sampler Particulate Sampler Effluent System Flow Rate Monitor Sampler Flow Rate Monitor M
R(2)
M R(2)
N.A.
N. A.
I N. A.
N.A.
N.A:
R N.A.
R
'(1)
Q(7)
N.A.
N.A.
Turbi'ne Building Ventilation Exhaust Monitor a.
Noble Gas Activity Monitor 1)
Low Range 2)
Intermediate Range b.
Iodine Sampler c.
Particulate Sampler d.
Effluent System Flow Rate Monitor e.
Sampler Flow Rate Monitor 0
0 W
D.
D N.A.
N. A.
N. A.
N.A.
R(2)
R(2)
N.A.
N. A.
Q(1)
Q(7)
N.A.
N. A.
Q
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fl
C)
INSTRUMENT TABLE 4.3.7. 12-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL
'MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE HECK HECK CA IBR i!ON TE T S
REIRUIRE AC:
5.
Radwaste Building Ventilation Exhaust a.
Noble Gas Activity Monitor 1)
Low Range 2)
Intermediate Range b.
Iodine Sampler c.
Particulate Sampler d.
Effluent System Flow Rate Measurement Device D(4)
N.A.'.A.
N. A.
R(2)
R(2)
N.A.
N.A.
R(6)
Q(i)
Q(7)
N.A.
N.A.
Q(5) e.
Sampler Flow Rate Monitor 6.
Main Condenser Offgas Treatment System Explosive Gas Monitoring System N.A..
R a.
Hydrogen Monitor N.A.
Q(3)
TABLE 4.3.7.12-1 (Continued)
TABLE NOTATIONS "At all times.
""Ouring main.condenser offgas treatment system operation.
(1)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
a.
Instrument indicates measured levels above the alarm setpoint.
b.
Circuit failure.
c.
Instrument controls not set in operate mode.
(2)
The initial CHANNEL CALIBRATION shall be performed using one or more reference radioactive standards traceable to the National Bureau of Standards:(NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
Subsequent CHANNEL CALIBRATION shall be performed using the initial radioactive standards or other standards of equivalent quality or radioactive sources that have been related to the initial calibration.
(3)
The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
a.
0.0 volume percent
2.0 volume percent
(4)
The CHANNEL CHECK shall be performed by comparing computer readings or comparing each fan's local amperage reading.
(5)
The CHANNEL FUNCTIONAL TEST shall be performed by measurement of the phase currents for each fan.
(6)
The CHANNEL CALIBRATION shall be performed by using a flow measurement device to determine the fan current to flow relationship.
(7)
For the CHANNEL FUNCTIONAL TEST on the intermediate range noble gas activity monitors, demonstrate that circuit failures or instrument controls when set in the OFF position produce control room alarm annunciation.
MASHINGTON NUCLEAR - UNIT 2 3/4 3-95 Amendment 4
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES n
m M
VALVE FUNCTION AND NUMBER a.
Automatic Isolation Valves (Continued)
Equipment Drain (Radioactive)
EDR-V-19 EDR-V-20 Floor Drain (Radioactive)
FDR-V-3 FDR-V-4 Fuel Pool Cooling/Suppression Pool Cleanup FPC-V-153(f)
FPC-V-154(f)
FPC-V-156 Reactor Recirculation Hydraulic Control(e)
HY-V-17A,B HY-V-18A,B HY-V-19A,B HY-V-20A,B HY-V-33A,B HY-V-34A,B HY-V-35A,B HY-V-36A,B Traversing Incore Probe Valve TIP-V-6,7,8,9,10 (Probe Line Ball Valves)
TIP-V-11 (Nz Gate Valve)
VALVE GROUP(a) l4 MAXIMUM ISOLATION TIME (Seconds) 15 15 35
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TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER VALVE GROUP(a) d.
Other Containment Isolation Valves (Continued)
Containment Purge System CSP-V-8 CSP-V-9 CSP-V-10 Reactor Recirculation (Seal Injection)
RRC-V-13A,B RRC-V-16A,B Containment Instrument Air CIA-.Y-20 CIA-V-21 CIA-V-30A,B CIA-V-31A,B Containment Air Supply CAS-V-453 Post-Accident Sampl ing System(c)
PSR-V-X73-1 PSR-V-X73-2 PSR-V-X77A1 PSR-V-X77A2 PSR-V-X77A3 PSR-V-X77A4 PSR-V-X80-1 MAXIMUM ISOLATION TIME (Seconds)
N. A.
N.A.
N. A.
15 22 N. A.
22 N.A.
N. A.
N.A.
ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS 4.8.1.1. 1 Each of the above required'ndependent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:
a.
Determined OPERABLE at least once per 7 days by.verifying correct breaker alignments and indicated power availability, and.
b.
Demonstrated OPERABLE at least once per 18 months during shutdown by transferring, manually and automatically, unit power supply from the normal circuit to the alternate circuit.
4.8.1.1.2 Each of the above required diesel generators shall be demonstrated OPERABLE:
a.
In accordance with the frequency specified in Table 4.8.1. 1.2-1 on a STAGGERED TEST BASIS by:
1.
Verifying the fuel level in the day fuel tank.
2.
- Verifying the fuel level in the fuel storage tank.
3.
Verifying the fuel transfer pump starts and transfers fuel from the storage'system to the day fuel tank.
4.
Verifying the diesel starts from ambient condition and accelerates to at least 900 rpm (60 Hz) in less than or equal to 10 seconds~
for DG-1 and DG-2 and 13 seconds~
for DG-3.
The generator voltage and frequency shall be 4160 + 420 volts and 60 + 3.0 Hz within 10 seconds~
for DG-1 and DG-2 and 13 seconds~
for DG-3 after the start signal.
The diesel generator shall be started for this test by using one of the following signals:
a)
Manual.
b)
Simulated loss-of-offsite power by itself.
c)
Simulated loss-of-offsite power in conjunction with an ESF actuation test signal.
d)
An ESF actuation test signal by itself.
5.
Verifying the diesel generator is synchronized, loaded to greater than or equal to 4400 kW for DG-1 and DG-2 and 2600 kW for DG-3 in less than or equal to 60 seconds~,
and operates with these loads for at least 60 minutes.
6.
Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.
7.
Verifying the pressure in all diesel generator air start receivers to be -greater than or equal to 230 psig for DG-1 and DG-2 and 200 psig for DG-3, b.
At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by checking for and removing accumulated water from the day fuel tanks.
~These diesel generator starts from ambient conditions shall be performed at
'least once per 184 days in these surveillance tests and all other engine starts for the purpose of this surveillance testing shall be preceded by an engine prelube period and/or other warmup procedures recommended by the manu-facturer so that mechanical stress and wear on the diesel engine is minimized.
WASHINGTON NUCLEAR -
UNIT 2 3/4 8"3 Amendment 4
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ELECTRICAL POWER SYSTEMS DISTRIBUTION SHUTDOWN LIMITING CONDITION FOR OPERATION 3'.3.2 As a 'minimum, the following power distribution system divisions shall be energized:
a.
For A.C. power distribution,. Division 1 or Division 2, and when the HPCS,>..-
system is required to be OPERABLE, Division 3, with:
b.
1.
Division 1, consisting of:
a) 4160-volt bus SH-7.
b) 480-volt bus SL-71 and SL-73.
c) 480-volt MCC's 7A, 7A-A, 7B, 7B-A, 7B-B, 7F.
d) 480-volt Power Panel PP-7A-B.
e) 120/208-volt 38 Power Panels PP-7A-G, PP-7A-A-A.
f) 120/240-volt 18 Power Panels PP-7A-A, PP-7A-F, PP-7A-E, and PP-7A.
2.
Division 2, consisting of:
a) 4160-volt bus SM-S.
b) 480-volt bus SL-81 and SI,-83.
c) 480-volt HCC's SA, SA-A, SB, SB-A, SB-B, SF.
d) 480-volt Power Panel PP-SA-B.
e) 120/208-volt 38 Power Panels PP-8A-G, PP-SA-A-A.
f) 120/240-volt 18 Power Panels PP-SA-A, PP-SA-F, PP-SA-E, and PP-BA.
3.
. Division 3, consisting of:
a) 4160-volt bus SM-4.
b) 480-volt 38 Engine
& Gen.
Aux. loads Power Panel.
c) 120/240-volt 18 Power Panel PP-4A.
d) 480"volt 38 MCC 4A.
For D.C.
power distribution, Division 1 or Division 2, and when the HPCS system is required to be OPERABLE, Division 3, with:
1.
Division 1, consisting of:
a) 125-volt D.C.
Main Distribution Panel Sl-l.
b) 125-volt VDC Motor Control Center MC-Sl-lD.
c) 125-VDC Instr.
and Control NSSS Bd. Distr.
Panel DP-Sl-lA.
d) 125-VDC Remote Shutdn.
Distr. Pnl. DP-Sl-lD.
e) 125-YDC Diesel Gen.
1 Dist. Pnl. DP-Sl-lE.
f) 250-VDC Hain Distribution Panel S2-1.
g) 250-VDC Motor Control Center MC-S2-1A, Part A and Part B.
h) 124-VDC Power Panel DP-SO-A.
i) 125-YOC Critical Swgr. Dist. Pnl.
DP-Sl-1F 2.
Division 2, consisting of:
a) 125-volt D.C. Main Distribution Panel S1-2.
b) 125-volt VDC Motor Control Center MC-S1-2D.
c) 125-VDC Instr.
and Control NSSS Distr.
Panel DP-S1-2A.
d) 125-VDC Critical Swgs.
& Remote Shutdn. Distr. Pnl.
DP-S1-20.
e) 125-VDC Diesel Gen.
2 Dist. Pnl.
DP-S1-2E.
f)
+24-YDC Power Panel DP-SO-B.
3.
Division 3, consisting of 125-volt D.C.
HPCS distribution panel.
WASHINGTON NUCLEAR - UNIT 2 3/4 8"18 Amendment 4
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REFUELING OPERATIONS 3/4. 9. 2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 At least 2 source range monitor~
(SRM) channels shall be OPERABLE and inserted to the normal operating level with:
a.
Continuous visual indication in the control
- room, b.
At least one with alarm in the control
- room, c.
One of the required SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent
- quadrant, and d.
The "shorting links" removed from the RPS circuitry prior to and during the time any control rod is withdrawn and shutdown margin demonstrations are in progress.
APPLICABILITY:
OPERATIONAL CONDITION 5.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS~ and insert all insertable control rods.
SURVEILLANCE RE UIREMENTS 4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE by:
a.
At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
1.
Performance of a CHANNEL CHECK, 2.
Verifying the detectors are'inserted to the normal operating
- level, and 3.
During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE ALTERATIONS are being performed and another is located in an adjacent quadrant.
The use of spec>al movable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible. as long as these 'special detectors are connected to the normal SRM circuits.
~"Except movement of IRM, SRM or special movable detectors.
Not required for control rods removed per Specification 3.9. 10. 1 and 3.9. 10.2.
MASHINGTON NUCLEAR - UNIT 2 3/4 9"3 Amendment 4
ADMINISTRATIVE CONTROLS 6.2.3 NUCLEAR SAFETY ASSURANCE GROUP (NSAG FUNCTION 6'.3.1 The NSAG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of similar
- design, which may indicate areas for improving unit safety.
The NSAG shall mak'e detailed recommendations for revised procedures, equipment and modifications, maintenance activities, operations activities, or other means of improving unit safety to the Director of Licensing and Assurance.
COMPOSITION 6.2.3.2 The NSAG shall be composed of at least five, dedicated, full-time engineers, a minimum of three located on site and two at the home office.
Each shall have a bachelor's degree in engineering or related science or qualifica-tions meeting ANS.3.1 Draft Revision dated March 13, 1981, Section 4.2 or 4.4, or equivalent,- as described in Section 4.1 and at least 2 years professional level experience in his field, at least 1 year of which experience shall be in the nuclear field.
RESPONSIBILITIES 6.2.3.3 The NSAG shall be responsible for maintaining surveillance of unit activities to provide independent 'verification~ tliat these activities are performed -correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the NSAG shall be prepared, main-
- tained, and forwarded each calendar month to the Director of Licensing and Assurance.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4. 1 The Shift Technical Advisor shall provide advisory technical support to the Shift Manager in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.
- 6. 3 UNIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI/ANS N18.1-1971 for comparable positions, except for the Health Physics/
Chemistry Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1-R, May 1977.
The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
~Not responsible for sign-off function.
MASHINGTON NUCLEAR - UNIT 2 6-7 Amendment 4